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Nuclear fuel alloys or mixtures and method of making thereof

Active Publication Date: 2016-04-05
THE UNITED STATES AS REPRESENTED BY THE DEPARTMENT OF ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Benefits of technology

The patent is about a new nuclear fission fuel mixture that can be used in fission reactors. The fuel mixture includes a naturally fissioning actinide, molybdenum, and other metals like magnesium, zirconium, or manganese. These metals are added in a specific way to create a solid phase diagram that ensures the fuel mixture stays below an upper temperature limit. The technical effect is a safer and more stable nuclear fission fuel mixture that reduces the risk of accidental melting or exploding.

Problems solved by technology

Whatever the geometry, any redistribution of the chemical components of a nuclear fuel slug inhibits accurate modeling and complicates efforts toward designing and implementing a nuclear fuel rod and predicting its performance over time.

Method used

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  • Nuclear fuel alloys or mixtures and method of making thereof
  • Nuclear fuel alloys or mixtures and method of making thereof
  • Nuclear fuel alloys or mixtures and method of making thereof

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Embodiment Construction

[0022]In various exemplary embodiments, nuclear fuel alloys or mixtures and methods of making nuclear fuel mixtures are provided. Pseudo-binary actinide-M fuel mixtures described herein are expected to form alloys and exhibit: body-centered cubic solid phases at advantageously low temperatures; high solidus temperatures; and / or minimal or no reaction or inter-diffusion with steel and other cladding materials. Methods described herein through metallurgical and thermodynamics advancements guide the selection of amounts of fuel mixture components by use of phase diagrams. For example, weight percentages for components of a metallic additive to an actinide fuel are selected in a solid phase region of an isothermal phase diagram, such as shown in FIG. 7, taken at a temperature below an upper temperature limit for the resulting fuel mixture in reactor use. The upper temperature limit can be the melting point of solid uranium (1135° C.), or above 1200° C., or preferably above 1250° C. Adva...

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Abstract

Nuclear fuel alloys or mixtures and methods of making nuclear fuel mixtures are provided. Pseudo-binary actinide-M fuel mixtures form alloys and exhibit: body-centered cubic solid phases at low temperatures; high solidus temperatures; and / or minimal or no reaction or inter-diffusion with steel and other cladding materials. Methods described herein through metallurgical and thermodynamics advancements guide the selection of amounts of fuel mixture components by use of phase diagrams. Weight percentages for components of a metallic additive to an actinide fuel are selected in a solid phase region of an isothermal phase diagram taken at a temperature below an upper temperature limit for the resulting fuel mixture in reactor use. Fuel mixtures include uranium-molybdenum-tungsten, uranium-molybdenum-tantalum, molybdenum-titanium-zirconium, and uranium-molybdenum-titanium systems.

Description

STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH OR DEVELOPMENT[0001]The United States Government has rights in this invention pursuant to Contract No. DE-AC07-05ID14517, between the U.S. Department of Energy (DOE) and Battelle Energy Alliance, representing Idaho National Laboratory (INL).FIELD OF THE DISCLOSURE[0002]The present disclosure relates generally to nuclear fission fuel compositions, and more particularly to metallic additives for use in nuclear fuel mixtures, and methods for selecting the additive species and amounts thereof.BACKGROUND OF THE DISCLOSURE[0003]Metals and alloys thereof are used in nuclear fuels to increase burn up (fuel utilization) and to gain beneficial chemical, thermal, and mechanical properties over pure or combined actinide fuels, such as uranium (U) and plutonium (Pu). For example, an additive is often mixed with uranium to form a pseudo-binary mixture “U-xM,” where “M” is a metallic additive, and “x” conveys relative amount information. The metalli...

Claims

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Application Information

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IPC IPC(8): G21C3/60
CPCG21C3/60C22C43/00Y02E30/30C22C1/12
Inventor MARIANI, ROBERT DOMINICKPORTER, DOUGLAS LLOYD
Owner THE UNITED STATES AS REPRESENTED BY THE DEPARTMENT OF ENERGY